Carbide-based fuel assembly for thermal propulsion applications

ABSTRACT

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC—SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a NTP reactor.

RELATED APPLICATION DATA

This application is a continuation application of U.S. patent application Ser. No. 17/399,881, filed Aug. 11, 2021, which is based on and claims priority under 35 U.S.C. § 119 to U.S. Provisional Application No. 63/090,383, filed Oct. 12, 2020, the entire contents of each of these applications are incorporated herein by reference.

STATEMENT REGARDING FEDERALLY SPONSORED RESEARCH OR DEVELOPMENT

the invention described herein was made in the performance of work under Subcontract 00212687 to DOE Award No. DE-AC07-051D14517 and NASA Prime Contract 80MSFC17C0006 and is subject to the provisions of section 2035 of the National Aeronautics and Space Act (51 U.S.C. § 20135). The Government has certain rights in this invention.

TECHNICAL FIELD AND INDUSTRIAL APPLICABILITY

The present disclosure relates generally to nuclear fission reactors and structures related to nuclear fission reactors, in particular for propulsion. Such nuclear propulsion fission reactors may be used in various non-terrestrial applications, such as space and ocean environments. In particular, the disclosure relates to a carbide-based fuel assembly that can be incorporated into a nuclear reactor for nuclear thermal propulsion and which is capable of heating hydrogen propellant to temperatures required to achieve specific impulse (I_(SP)) values in the range of 900 to 1000 seconds, alternatively 950 to 1000 seconds. The fuel assembly includes uranium-bearing fuel elements, preferably using high-assay low-enriched uranium (HALEU), and a carbide-based insulator and other structural material.

BACKGROUND

In the discussion that follows, reference is made to certain structures and/or methods. However, the following references should not be construed as an admission that these structures and/or methods constitute prior art. Applicant expressly reserves the right to demonstrate that such structures and/or methods do not qualify as prior art against the present invention.

Various propulsion systems for non-terrestrial applications, such as in space, have been developed. A typical design for a nuclear thermal propulsion (NTP) reactor and engine 10 is shown in FIG. 1 . The illustrated nuclear thermal propulsion reactor and engine 10 includes four main features: a vessel 20 having a reactor 22 contained within a reflector 24, turbomachinery 30 including turbo pumps 32 and other piping and support equipment 34, shielding 40 (which is shown as internal shielding in between the turbomachinery 30 and the vessel 20, but can also be external shielding), and a nozzle section 50 including a nozzle 52 and a nozzle skirt 54.

Various fuel element structural and fuel materials have been considered. Typically, prior nuclear rocket programs utilized high-enriched (weapons grade) uranium (HEU), enriched to around 90% U-235. In one example, coated uranium carbide particles or uranium carbide-zirconium carbide particles were dispersed in a graphite matrix that was coated with zirconium carbide or niobium carbide to prevent hydrogen erosion of the graphite. A hydrogen propellant/coolant temperature of 2550K was reached during integrated nuclear engine testing. In another example, a cermet fuel consisting of uranium oxide embedded in a refractory metal matrix was used.

Structural forms for NTP reactors have, in one example, included particle bed reactors (PBR), in which the hydrogen propellant flowed radially through a bed of coated UC_(x) fuel particles and then axially outward from the center of the fuel element into the nozzle chamber, and in a second example, included propellant/coolant flowing axially over bundles of fuel rods.

Despite the state of the art for NTP reactors, there remains a need for improved designs, and particularly designs that incorporate HALEU fuel, and manufacturing techniques to realize propulsion systems for NTP applications that balance thrust, specific impulse, and mass to provide performance that is tailored to specific missions.

SUMMARY

Presently, there is a need for improvements directed to NTP applications in which the specific impulse is in the range of 900 to 1000 seconds. This translates to propellant (i.e., hydrogen propellant) exit temperatures from the reactor in excess of 2700K (kelvin), and thus fuel temperatures in excess of 2900K. In example embodiments utilizing hydrogen propellant, exit temperature of the hydrogen propellant is on the order of 2950K for a specific impulse of 950 seconds.

Additionally, there is a need to implement HALEU fuels, so as to reduce or eliminate the use of HEU fuel. However, reactors using HALEU fuel require significant neutron moderation to produce a thermal neutron energy spectrum.

In general, the disclosure is directed to a nuclear fission reactor structure suitable for use in a nuclear-based propulsion system, such as nuclear thermal propulsion. In exemplary embodiments, the nuclear fission reactor structure utilizes a carbide-based fuel assembly containing one or more uranium-bearing fuel elements. The carbide-based fuel assembly includes a fuel assembly outer structure and also includes a carbide-based insulation layer interposed between an inner surface of the fuel assembly outer structure and one or more uranium-bearing fuel elements located in the assembly. One or more carbide-based support meshes are positioned at the longitudinal ends of the fuel element and can also separate the fuel elements into sections.

The form of the fuel element is not particularly limited. In some embodiments, the fuel element is in the form of a plurality of individual elongated fuel bodies, such as rods or rodlets, arranged in a fuel bundle. In other embodiments, the fuel element is in the form of one or more fuel monolith bodies containing flow channels for coolant. In some aspects, there is one fuel monolith body, in other aspects, there is more than one fuel monolith body. The fuel monolith body can be in a suitable shape(s) for assembling into the space within the fuel assembly occupied by the one or more fuel elements. For example, fuel monolith bodies having the shape of wafers, layers, pie-shaped sections, and cylinders can be utilized and arranged next to each other in a single layer and/or stacked on each other in multiple layers.

Preferably, the fuel element uses a fuel composition including HALEU.

In NTP applications, the nuclear fission reactor structure is housed in the vessel of a nuclear thermal propulsion reactor and engine. Propulsion gas is used as a coolant for the nuclear fission reactor structure. Propulsion gas heated in the active core region of the nuclear fission reactor structure exits through a nozzle and generates thrust.

An embodiment of carbide-based fuel assembly comprises a fuel assembly outer structure, a fuel assembly intermediate structure, a first fuel element contained within the fuel assembly intermediate structure, an insulation layer interposed between an inner surface of the fuel assembly outer structure and the outer surface of the fuel assembly intermediate structure, a first void space between an outer surface of the insulation layer and the inner surface of the fuel assembly outer structure; and a second void space between an inner surface of the insulation layer and the outer surface of the fuel assembly intermediate structure. The first fuel element includes one or more fuel bodies containing a fuel composition and a coolant flow volume thorough which a coolant in a form of a propellant gas flows during operation of a reactor containing the carbide-based fuel assembly. The fuel assembly intermediate structure is spaced apart from an outer envelope surface of the first fuel element and extends between a first end surface of the first fuel element and a second end surface of the first fuel element, an inner surface of the fuel assembly intermediate structure is oriented toward the first fuel element, and an outer surface of the fuel assembly intermediate structure is oriented away from the first fuel element.

In one aspect, the first fuel element includes a plurality of individual elongated fuel bodies, such as fuel rods, each of which contains a fuel composition and is elongated and longitudinally extends from a first end to a second end along a longitudinal axis of the respective elongated fuel body. The plurality of elongated fuel bodies are arranged in spaced-apart relationship relative to each other in a fuel bundle. Within the fuel bundle, the plurality of elongated fuel bodies are located at positions that are axisymmetric about the longitudinal axis of the carbide-based fuel assembly, as seen in cross-section in a plane perpendicular to the longitudinal axis of the carbide-based fuel assembly, and an empty space between the spaced-apart elongated fuel bodies in the fuel bundle is a coolant flow volume thorough which a coolant in the form of a propellant gas flows during operation of a reactor containing the carbide-based fuel assembly.

In another aspect, the first fuel element includes one or more fuel monolith bodies. Each fuel monolith body contains a fuel composition and includes one or more coolant flow channels. One or more coolant flow channels is a coolant flow volume thorough which a coolant in a form of a propellant gas flows during operation of a reactor containing the carbide-based fuel assembly. The one or more fuel monolith bodies can be in any suitable shape, such as a wafer, a layer, a pie-shaped section, or a cylinder, and these shapes can be arranged next to each other in sections or in a layer, stacked on top of each other, or otherwise positioned to form the fuel element.

In additional aspects, the outer surface of the fuel assembly outer structure includes (a) a layer having a composition including a refractory ceramic material, (b) a spacer structure projecting from the outer surface, or a combination of (a) and (b). In still additional aspects, the outer surface of the fuel assembly intermediate structure includes one or more ribs projecting outward from the outer surface of the fuel assembly intermediate structure and/or the inner surface of the fuel assembly intermediate structure includes one or more ribs projecting outward from the inner surface of the fuel assembly intermediate structure, in each case the one or more ribs extend axially along a longitudinal length of the fuel assembly intermediate structure or extend helically along a longitudinal length of the fuel assembly intermediate structure. In still further embodiments, the inner surface of the insulation layer can include one or more ribs extending axially or helically along a longitudinal length of the insulation layer to create the void between the insulation layer and the outer surface of the intermediate structure. Features from additional embodiments may be used individually or in combination.

Disclosed carbide-based fuel assemblies can be incorporated into a nuclear fission reactor structure. An example embodiment of a nuclear fission reactor structure comprises a moderator block including a plurality of fuel assembly openings and a plurality of the carbide-based fuel assemblies. Each of the plurality of carbide-based fuel assemblies is located in a different one of the plurality of fuel assembly openings. In a cross-section of the moderator block perpendicular to the longitudinal axis of the nuclear fission reactor structure, the plurality of carbide-based fuel assemblies are distributively arranged in the moderator block.

Embodiments of the nuclear fission reactor structure can be incorporated into a nuclear thermal propulsion engine. An example nuclear thermal propulsion engine comprises the disclosed nuclear propulsion fission reactor structure, shielding, a reservoir for cryogenically storing a propulsion gas, turbomachinery, and a nozzle. In a flow path of the propulsion gas, the shielding, the turbomachinery, and the reservoir are operatively mounted upstream of the inlet connection assembly of the carbide-based fuel assemblies, and the nozzle is operatively mounted downstream of the outlet connection assembly of the carbide-based fuel assemblies. The nozzle provides a flow path for heated propulsion gas exiting the nuclear propulsion fission reactor structure.

BRIEF DESCRIPTION OF THE DRAWINGS

The foregoing summary, as well as the following detailed description of the embodiments, can be better understood when read in conjunction with the appended drawings. It should be understood that the embodiments depicted are not limited to the precise arrangements and instrumentalities shown.

FIG. 1 illustrates structure and arrangement of features in a typical design for a nuclear thermal propulsion reactor and engine.

FIGS. 2A and 2B schematically illustrate, in a longitudinal cross-sectional view, an embodiment of a carbide-based fuel assembly.

FIGS. 3A-3B schematically illustrate aspects of an embodiment of a carbide-based fuel assembly, in particular features at a first end of the carbide-based fuel assembly (in dissembled view at section A-A in FIG. 2A) and at a cross-section (at section B-B in FIG. 2A).

FIG. 4A is a longitudinal cross-sectional view of a portion of an embodiment of a carbide-based fuel assembly and FIG. 4B is a magnified view of region P5 in FIG. 4A schematically showing, in cross-section, details associated with the structure of the carbide-based fuel assembly.

FIG. 5 schematically illustrates, in a radial cross-sectional view, an embodiment of carbide-based fuel assemblies in a nuclear fission reactor structure.

FIG. 6 is a flow chart of an example method of manufacturing a carbide-based fuel assembly.

FIG. 7 is a schematic, cross-sectional, side view of an embodiment of a nuclear propulsion fission reactor structure within a vessel.

FIG. 8 is a schematic, cross-sectional, top view of an embodiment of an embodiment of a nuclear propulsion fission reactor structure within a vessel.

For ease of viewing, in some instances only some of the named features in the figures are labeled with reference numerals.

DETAILED DESCRIPTION

FIGS. 2A and 2B schematically illustrate, in a longitudinal cross-sectional view, an embodiment of a carbide-based fuel assembly. FIG. 2B is a magnified view of region P4 of FIG. 2A. The exemplary carbide-based fuel assembly 100 includes one or more fuel elements 105 that are contained within a fuel assembly outer structure 110 and, more specifically, are contained within a fuel assembly intermediate structure 250, as can also be seen and are further disclosed in connection with the magnified views in FIGS. 4A and 4B.

In FIGS. 2A and 2B, the fuel elements 105 have an elongated, longitudinally slender form extending from a first end to a second end along a longitudinal axis of the respective fuel element. Typically, the longitudinal axis of the individual elongated fuel bodies extends in a direction that is parallel to other structures in the fuel assembly, such as the fuel assembly outer structure 110, the fuel assembly intermediate structure 250, or the longitudinal axis 140 of the carbide-based fuel assembly 100. Although the term “rod” is used herein in connection with the fuel element 105, the cross-sectional shape in a plane perpendicular to the longitudinal axis of the fuel element 105 is not limited and can be any suitable shape, including a polygon (such as a triangle, a quadrilateral, a pentagon, a hexagon, a heptagon, an octagon, a nonagon, a decagon, a hendecagon, and a dodecagon), a circle, and an oval. Preferably the cross-sectional shape of the fuel element is a regular polygon, although irregular polygons can also be utilized. In addition, the cross-sectional shape can change along the length of the fuel element rod—in some instances, continuously increasing or decreasing as a function of position or increasing at the longitudinal ends and decreasing between the ends, e.g., in a dog-bone shape or hourglass shape (as seen from a side view).

The plurality of fuel elements 105 contained within the fuel assembly outer structure 110 are in spaced-apart relationship relative to each other. The spaced-apart relationship between the individual fuel elements 105 and the empty space therebetween defines a volume, also called herein a coolant flow volume 115, through which coolant, in the form of propellant gas, flows during operation of a NTP reactor containing the carbide-based fuel assembly 100.

Also, while in the illustrated embodiment in FIGS. 2A-B the fuel elements 105 are rods and the coolant flowing though the coolant flow volume 115 contacts exterior surfaces of the fuel elements 105, the fuel element(s) 105 can have other forms as disclosed herein. For example, if in the form of a fuel monolith body, FIGS. 2A-B would schematically illustrate fuel-bearing material 105 in the fuel monolith body and the flow volume 115 would be in the form of a plurality of flow channels in the fuel monolith body through which coolant flows, which results in the coolant flowing though the coolant flow volume 115 contacting the inner diameter surface of the flow channels that are interior to the fuel monolith body.

The fuel elements 105 can be of various compositions. In general, the fuel elements 105 within the carbide-based fuel assembly 100 have a composition that comprises a fuel composition including HALEU. In particular embodiments, the HALEU has a U-235 assay above 5 percent and below 20 percent. In optional embodiments, the fuel elements 105 have a theoretical density of 95% or greater. In addition, the fuel elements 105 with a carbide-based composition can be refractory carbide coated and the fuel elements 105 with a cermet-based composition can be refractory metal coated.

In some embodiments, such as when the fuel element is in the form of an elongated fuel body, the fuel composition includes a binary carbide containing uranium or a ternary carbide containing uranium. Examples of a binary carbide containing uranium include (U,Zr)C, such as UC—ZrC. Examples of a ternary carbide containing uranium include (U,Zr,Nb)C, such as UC—ZrC—NbC.

In some embodiments, such as when the fuel element is in the form of a carbide-based fuel monolith body, the fuel composition includes a binary carbide containing uranium or uranium nitride. Examples of a binary carbide containing uranium include (U,Zr)C, such as UC—ZrC. The fuel monolith body includes a carbide matrix in which the fuel composition is distributed. Alternatively, the fuel monolith body includes a refractory metal matrix in which the fuel composition is distributed (i.e., a cermet monolith). Depending on the peak fuel temperatures of the nuclear reactor for nuclear thermal propulsion in which the fuel element in the form of a cermet monolith body is used, other fuel compositions can be used. For example, for reactors designed to operate with peak fuel temperatures below about 2850K, uranium oxide or uranium nitride can be used as the fuel material in the fuel composition in the refractory metal matrix, while for reactors designed to operate with peak fuel temperatures above about 2850K, uranium nitride can be used as the fuel material in the fuel composition in the refractory metal matrix.

Also, the disclosed carbide-based fuel assembly structure is not restricted to assemblages of carbide-based fuel rods, and the structures and functions disclosed herein for the assemblages of carbide-based fuel rods can also be applied to monolithic carbide fuel elements containing flow channels or monolithic cermet fuel elements containing flow channels. For example, the fuel composition can be in the form of a ceramic-ceramic (cercer) composite, such as uranium nitride fuel embedded within a ZrC_(x) matrix phase. In one particular embodiment, the composition of the cercer fuel includes uranium nitride with ZrC_(x). In another particular embodiment, the composition of the cercer fuel includes (U,Zr)C with ZrC_(x). Also for example, the fuel composition can be in the form of a cermet, such as uranium nitride fuel within a W or Mo (or mixtures thereof) matrix. In one particular embodiment, the composition of the cermet fuel includes uranium nitride, tungsten, and molybdenum. In another particular embodiment, the composition of the cermet fuel includes uranium oxide, tungsten, and molybdenum.

FIG. 3A illustrates cylindrical fuel elements 105, but the fuel elements 105 can be made in other geometries, as noted herein. In addition, shapes of the fuel elements 105 can be used that (a) increase surface area to volume ratio, (b) interlock with each other, and (c) enhance propellant/cooling mixing (such as with a twisted shape). For example, a twisted ribbon design for the fuel elements 105 can create sufficient openings between the fuel elements 105 for coolant flow, in which case, there may be no need to include other means to create a flow passages between the individual fuel elements 105. Also, the composition and/or length of the fuel elements 105 can be selected to facilitate axial zoning to provide a desired axial power profile.

Although not shown in FIGS. 3A and 3B, in some embodiments, the plurality of fuel elements 105 and the coolant flow volume 115 are contained within a fuel assembly intermediate structure 250, which itself is contained within the fuel assembly outer structure 110 (with other intervening structures and spacing, as further disclosed herein) (see, e.g., FIGS. 4A and 4B and FIG. 5 ).

In exemplary embodiments, the fuel assembly outer structure 110 is formed of a ceramic matrix composite (CMC) material. An example suitable CMC material is a SiC—SiC composite. A SiC—SiC composite has a silicon carbide (SiC) matrix phase and a silicon carbide (SiC) fiber phase incorporated together. A SiC—SiC composite is preferred for the fuel assembly outer structure 110. Desirable properties of SiC—SiC composite materials include high thermal, mechanical, and chemical stability and a high strength to weight ratio. Advantageous properties of SiC—SiC composite materials for nuclear applications include damage tolerance (non-brittle failure behavior), relatively low thermal conductivity, mechanical properties that are retained to temperatures exceeding 1500K, and not being adversely affected by neutron irradiation. Furthermore, SiC is not a parasitic neutron absorber and the carbon atoms provide some amount of neutron moderation.

As seen in FIG. 2A, the fuel assembly outer structure 110 connects an inlet flow adapter 120 (at a first end of the carbide-based fuel assembly 100) to an outlet flow adapter 125 (at a second end of the carbide-based fuel assembly 100). The inlet flow adapter 120 can be attached to the upper end of the fuel assembly outer structure 110. In some embodiments, the upper end of the fuel assembly outer structure 110 is brazed to a metal component prior to loading fuel into the carbide-based fuel assembly 100. Afterward, the inlet flow adapter 120 can be mechanically attached to the brazed metal component. In some embodiments, the outlet flow adapter 125 can be attached to the lower end of the fuel assembly outer structure 110 by a mechanical means, or alternatively via brazing. In other embodiments, the outlet flow adapter 125 can be incorporated into the fuel assembly outer structure 110 during manufacture, i.e., the outlet flow adapter 125 can be an integral part of the fuel assembly outer structure 110. Also, the lower end of the fuel assembly outer structure 110 and the outlet flow adapter 125 interface with a support plate for mounting the carbide-based fuel assembly 100 within a reactor structure.

In some embodiments, the plurality of fuel elements 105 constitute a bundle (also called herein a “fuel element bundle” or “fuel bundle”), which is contained within a single section within the fuel assembly outer structure 110. In other embodiments, multiple sections (each containing a bundle of the plurality of fuel elements 105) are contained within the fuel assembly outer structure 110. Each section, e.g., section A and section B shown in FIG. 2A, is contained within a fuel assembly intermediate structure 250, which extends along the length of the side perimeter of the section. For example, the fuel assembly intermediate structure 250 extends between a first end surface of the fuel element bundle and a second end surface of the fuel element bundle. The individual sections, such as sections A and B in FIG. 2A, are separated by a support mesh 150. For example, each section in the carbide-based fuel assembly 100, e.g., section A and section B, is bounded at a first end and at a second end by a support mesh 150. Thus, a first support mesh is located at the first end surface of the first fuel element bundle and a second support mesh is located at the second end surface of the first fuel element bundle.

In embodiments with multiple sections, there is a corresponding fuel assembly intermediate structure 250 extending along the length of the side perimeter of the section, with one end of the fuel assembly intermediate structure 250 abutting the first support mesh 150 and another end of the fuel assembly intermediate structure 250 abutting the second support mesh 150. If a second section is present, then the second fuel element bundle is separated from the first fuel element bundle in a longitudinal direction by one of the first support mesh 150 and the second support mesh 150 (depending on the location of the second fuel element bundle relative to the first second fuel element bundle, i.e., adjacent the first end surface or adjacent the second end surface of the first fuel element bundle). Each section has a corresponding fuel assembly intermediate structure 250 that is separate from the fuel assembly intermediate structure 250 of an adjacent section. In addition, a third support mesh 150 can be located at an opposite end of the second fuel element bundle from the one first or second support mesh separating the second fuel element bundle from the first fuel element bundle. Further, in arrangements with either a single section or multiple sections, a support mesh 150 is typically included at the first end of the carbide-based fuel assembly 100 (in the area of the inlet flow adapter 120) and at the second end of the carbide-based fuel assembly 100 (in the area of the outlet flow adapter 125).

The support mesh 150 is a structure traversing the inner volume of the fuel assembly 100 (typically in a plane perpendicular to the longitudinal axis 140 as seen in FIG. 2A and FIG. 4A). In some embodiments, the support mesh 150 traverses the inner volume defined by the inner surface of the fuel assembly outer structure 110; in other embodiments, the support mesh 150 traverses the inner volume defined by the inner surface of the insulation layer 160. FIG. 3A schematically illustrates a disassembled, perspective, view of a first end of a carbide-based fuel assembly taken along section A-A in FIG. 2A and schematically illustrates an embodiment of a support mesh 150. In FIG. 3A, the support mesh 150 is seen in plan view looking along longitudinal axis 140 (as opposed to the edge plan view, i.e., perpendicular to longitudinal axis 140, of the support mesh 150 as shown in FIG. 2A and FIG. 4A). The support mesh 150 includes openings 152 traversing a thickness of the support mesh 150 to allow coolant flow through the support mesh 150. For example, the openings 152 in the support mesh 150 are configured to allow coolant flowing through the carbide-based fuel assembly 100 from entrance opening 130 and out through exit opening 135 to flow through the openings 152 in the support mesh 150. The support mesh 150 is sufficiently sized and constructed so as to allow coolant traveling through the carbide-based fuel assembly 100 to pass through the support mesh 150 while the support mesh 150 also holds the one or more fuel elements 105 in place axially (i.e., relative to the longitudinal axis 140). For example, the support mesh 150 includes a first region 156 having the openings 152 traversing the thickness of the support mesh 150. The characteristics of the openings 152, such as size, location and tortuosity of the path from a first side to a second side of the support mesh 150, are selected so that there is minimal differential pressure drop for the coolant traveling through the openings 152. For example, in some embodiments, the structure of the support mesh will be designed such that the open area for coolant flow through the support mesh will be greater than that defined for the coolant flow volume 115. Also for example, in some embodiments, the pressure drop for the coolant traveling through the openings 152 is in the range of 30 to 100 psi (about 206 KPa to 690 KPa). Secondarily, the openings 152 are interconnected internally within the body of the first region 156 so as to allow coolant mixing, which can contribute to reduce the radial temperature gradients within successive fuel element sections.

The support mesh 150 can include an optional outer region 158. The outer region 158 can enclose the first region 156, which thereby is effectively an interior region relative to the outer region 158. For example, depending on the geometric shape of the first region 156, the outer region 158 can enclose a perimeter of the first region 156. Where the geometric shape of the first region 156 is circular, the outer region 158 can circumferentially enclose the first region 156 and the first region 156 can effectively be a radially interior region. In one aspect, the outer region 158 can have a higher density (lower porosity) than the first region 156. In another aspect, the outer region 158 can be devoid of openings. In either aspect, the mechanical strength of the outer region 158 is designed to support the weight and forces related to stacking a first section of one or more fuel elements 105 on a second section of one or more of fuel elements 105 (as shown in, e.g., FIG. 2A with regard to section A and section B).

The support mesh 150 can be formed from any suitable material for the temperatures and forces expected during use of the carbide-based fuel assembly 100 in a NTP reactor and which is chemically stable in contact with other components of the fuel assembly. For example, the support mesh 150 can be formed of a refractory ceramic material. An example refractory ceramic material is zirconium carbide or niobium carbide. In exemplary embodiments, the refractory ceramic material includes pores separated by continuous carbide ligaments. In exemplary embodiments, the porosity of the support mesh 150 is in the range of 30-70%, alternatively in the range of 40-60%. For both zirconium carbide and niobium carbide, it is preferable that the material be near-stoichiometric (i.e., has a carbon to metal ratio above 0.95). Typically, the porosity of the support mesh 150 will be less than the porosity of the insulation material 160.

The openings 152 in the support mesh 150 can be formed by suitable means. For example, the support mesh 150 can be formed as an open cell structure where the open cells forming the openings 152 are formed during the manufacturing process of the body of the support mesh. Examples include refractory ceramic material that is 90% to 99.999%, alternatively 95% to 99.999% or 99% to 99.999%, zirconium carbide or niobium carbide in the form of an open-cell foam structure. Alternatively, the support mesh 150 can be formed as a solid body and the openings subsequently formed by chemical or mechanical processes, such as etching or machining. In one specific embodiment, the support mesh 152 is formed in an additive manufacturing process and both the body of the support mesh and the openings are formed during the manufacturing process as an integral unit.

In FIGS. 3A and 3B, the first end surfaces 170 of the fuel elements 105 (in this case, in the form of a plurality of fuel rods) are visible within the fuel assembly outer structure 110. Also visible is the radial distribution of the individual fuel elements 105. In the illustrated radial distribution, a central fuel element 105 a is located substantially (i.e., within manufacturing tolerances) coaxial with the longitudinal axis 140 of the carbide-based fuel assembly 100 and the remaining fuel elements 105 are located, in spaced-apart relation, at positions that are axisymmetric to the central fuel element 105 a. The empty space between the fuel elements 105 defines the coolant flow volume 115 thorough which coolant, in the form of propellant gas, flows during operation of a NTP reactor containing the carbide-based fuel assembly 100. Additionally, the FIG. 3B view is from the viewpoint of along the longitudinal axis 140 of the carbide-based fuel assembly 100 (which, in this case, is co-axial to the longitudinal axis of a center fuel element 105 a) and a surface of a second support mesh 150 b is visible through the coolant flow volume 115.

Further visible in FIGS. 3A and 3B is the insulation layer 160, which in the illustrated embodiment is conformal to and in contact with the inner surface of the fuel assembly outer structure 110. In other embodiments (see, e.g., FIGS. 4A and 4B), the insulation layer 160 can be spaced apart from both the inner surface of the fuel assembly outer structure 110 (forming a first void space) and the outer surface of the fuel assembly intermediate structure 250 (forming a second void space).

As indicated by arrow 180, the support mesh 150 is fitted into the space formed by a longitudinal extension of the fuel assembly outer structure 110 and insulation layer 160 that extends past the end surfaces 170 of the fuel elements 105.

Various details associated with the structure of the carbide-based fuel assembly are schematically illustrated in FIGS. 4A and 4B, which are a longitudinal cross-sectional view of a portion of an embodiment of a carbide-based fuel assembly (FIG. 4A) and a magnified view of region P5 (FIG. 4B), respectively.

For example, the carbide-based fuel assembly 100 includes a plurality of fuel elements 105. Consistent with descriptions herein, the fuel elements 105 are contained within a section of the carbide-based fuel assembly 100 in spaced-apart relation and form a fuel element bundle, such as the fuel element bundle shown at 190 b. The envelope surface containing the fuel element bundle 190 b is bounded by a support mesh 150 b at a first end, a support mesh 150 c at a second end, and a fuel element intermediate structure 250 b extending along the length of the side perimeter. The fuel element intermediate structure 250 b can be a thin-walled structure, such as a tube. The fuel element intermediate structure 250 b extends along the length of the side perimeter of the envelope surface bounding the fuel element bundle 190 b. The inner surface of the fuel assembly intermediate structure 250 b is oriented toward the plurality of fuel elements 105 and the outer surface of the fuel assembly intermediate structure 250 b is oriented away from the plurality of fuel elements 105 (e.g., toward the inner surface of the insulation layer 160 or the inner surface of the fuel assembly intermediate structure 250).

In one example, the fuel is a plurality of elongated fuel elements 105. Consistent with descriptions herein, the fuel elements 105 are contained within a section of the carbide-based fuel assembly 100 in spaced-apart relation and form a fuel element bundle, such as the fuel element bundle shown at 190 b in FIGS. 4A-B. In another example, the fuel is one or more fuel monolith bodies 200 (see FIG. 5 ). Consistent with descriptions herein, the one or more fuel monolith bodies 200 are contained within a section of the carbide-based fuel assembly 100, such as in place of the fuel element bundle shown at 190 b in FIGS. 4A-B.

In general, the inner surface of the fuel element intermediate structure 250 b is spaced-apart from the fuel. In embodiments in which the fuel form is individual elongated fuel bodies, this spacing allows coolant traveling through the coolant flow volume 115 to be in contact with the outer circumference surface of the fuel elements 105, including that portion of the outer circumference surface that is facing/located closest to the fuel assembly intermediate structure 250 b, e.g., radially closest in direction R relative to the longitudinal axis 140 of the carbide-based fuel assembly 100. In embodiments in which the fuel form is one or more monolithic fuel bodies, the spacing is minimized and, when present, is without coolant flow.

Other sections of the carbide-based fuel assembly 100 having fuel element bundles (190 a, 190 c) are also shown in FIG. 4A. In a direction of the longitudinal axis 140 of the carbide-based fuel assembly 100, the fuel element bundles are separated from each other by support meshes 150. If present, other fuel element bundles, e.g., 190 a, 190 c, also include similar features to those associated with fuel element bundle shown at 190 b.

As previously noted, in the various embodiments disclosed herein, the fuel element bundles with fuel elements 105 can, in alternative embodiments, be a solid, unitary body, i.e., fuel monolith, having fuel particles distributed within a matrix phase and having a plurality of coolant channels.

The fuel assembly intermediate structure 250 is formed of a refractory ceramic-graphite composite material. In some embodiments, the refractory ceramic-graphite composite material has a sufficiently high content level of the refractory ceramic component so as to form a continuous network of the refractory ceramic within the fuel assembly intermediate structure. For example, the refractory ceramic-graphite composite material has a refractory ceramic content of at least 60%, alternatively at least 65% and up to 95%, alternatively up to 90%. A suitable refractory ceramic-graphite composite material for the fuel assembly intermediate structure is zirconium carbide-graphite or niobium carbide-graphite. Niobium carbide-graphite is preferable for the higher temperature regions of the carbide-based fuel assembly 100. Without being bound to a particular theory, during reactor operation, it is anticipated that carbon (graphite) on the inner surface of the fuel assembly intermediate structure 250, i.e., the surface oriented toward the fuel element bundle, will lose carbon as a result of reaction with hydrogen coolant to form methane. This will particularly be the case toward the hot end of the fuel assembly 100. A fuel assembly intermediate structure 250 having a continuous refractory ceramic phase will be able to withstand the loss of some carbon and maintain its physical form. Thus, in the absence of a continuous refractory ceramic phase, the inner surface of the fuel assembly intermediate structure 250 may experience excessive erosion.

The shape of the fuel assembly intermediate structure 250 can be any shape that encloses the side surface of the perimeter of the respective fuel (whether in the form of individual elongated fuel elements 105 or in the form of a solid, unitary body 200). The fuel assembly intermediate structure 250 can be formed by extruding the shape, such as a tube, and sintering. The manufactured fuel assembly intermediate structure can be assembled into the carbide-based fuel assembly 100 by sliding the fuel assembly intermediate structure 250 into position about the side perimeter of the respective fuel by using the open ends of the fuel assembly intermediate structure 250. Once in place about the fuel, the fuel assembly intermediate structure 250 is positioned interposed between the insulation layer 160 (that is outward of the fuel assembly intermediate structure) and the fuel (that is inward of the fuel assembly intermediate structure 250) and contributes to protecting the insulation layer 160 from direct contact with the fuel. Additionally, the extruded shape—which has a general shape including a continuous connected side surface with open ends—also facilitates fabrication of the carbide-based fuel assembly 100.

There can be a separation distance between the inner surface of the fuel assembly intermediate structure and the fuel. However, such a separation distance is more commonly used where the fuel is in the form of individual fuel elements 105. There can also be a separation distance between the outer surface of the fuel assembly intermediate structure and the insulation layer 160. The various separation distances between the adjacent components contributes to improved thermal insulation or heat transfer performance of the carbide-based fuel assembly 100, either by the spaced-apart relationship, non-flowing gas, coolant flow, or a combination thereof.

For example, void space 255 between the inner surface of the insulation layer 160 and the outer surface of the fuel assembly intermediate structure may contain (non-flowing) hydrogen gas and can provide additional thermal insulation properties. Also for example, there is a space between the inner surface of the fuel assembly intermediate structure and the side envelope surface of the fuel, such as the nearest fuel element rod(s) 105 at the outer edge of the fuel element bundle 190 a, 190 b, or 190 c, or the outer side surface of the one or more fuel monolith bodies 200. In the case of elongated fuel bodies, such as fuel element rods 105, this space is part of the coolant flow volume 115 and coolant traveling through the coolant flow volume 115 will also travel through this space and proved a cooling function to both the fuel assembly intermediate structure 250 and the fuel element bundle, such as the nearest fuel element(s) 105. FIGS. 4A and 4B illustrate an embodiment of these separation distances and spaced-apart arrangements.

One or both of the surfaces of the fuel assembly intermediate structure 250, i.e., inner surface and outer surface, can optionally include a spacer structure to help form and maintain the noted separation distances and spaced-apart arrangements. For example, the inner surface of the fuel assembly intermediate structure 250 optionally includes one or more spacer structures to provide a defined and controlled space between the fuel assembly intermediate structure and the fuel. Also for example, the outer surface of the fuel assembly intermediate structure 250 optionally includes one or more spacer structures to provide a defined and controlled void space 255 between the fuel assembly intermediate structure and the insulation layer 160. In example embodiments, the spacer structure(s) can be one or more ribs projecting outward from the surface of the fuel assembly intermediate structure, either the inner surface (in the case of the space between the inner surface of the fuel assembly intermediate structure and the fuel) or the outer surface (in the case of the void space 255 between the fuel assembly intermediate structure 250 and the insulation layer 160). The one or more ribs can extend axially along a longitudinal length of the fuel assembly intermediate structure or can extend helically along a longitudinal length of the fuel assembly intermediate structure. The one or more ribs can extend continuously or discontinuously. Examples of ribs 260 in void space 255 are schematically illustrated in FIG. 5 .

The one or more ribs can be manufactured by suitable methods. For example, the ribs can be extruded with the fuel assembly intermediate structure, in which case the ribs are integral to the fuel assembly intermediate structure. Also, for example, the ribs can be separately formed and attached to the surface of the fuel assembly intermediate structure. In additional examples, the ribs can be a separate structure from the fuel assembly intermediate structure, such as a corrugated structure that is, e.g., sleeved with the fuel assembly intermediate structure. Depending on the fuel form, e.g., shape, it may not be appropriate to include axial ribs on the inner surface of the fuel assembly intermediate structure because, for example, the fuel element rods may be able to fit between the ribs and thereby be displaced from the distributive arrangement and/or become in contact with the fuel assembly intermediate structure. Therefore, an alternative arrangement for the ribs is as one or more spirals around the inner surface of the fuel assembly intermediate structure 250.

An insulation layer 160 is positioned outward (in direction R) of the fuel assembly intermediate structure 250. The inner surface of the insulation layer 160 is spaced apart from the outer surface of the fuel assembly intermediate structure 250. The insulation layer 160 extends at least between the end surfaces of the fuel element bundles and preferably extends the entire length from first end to second end of the carbide-based fuel assembly 100.

The insulation layer 160 can be formed from any suitable material for the temperatures and forces expected during use of the carbide-based fuel assembly 100 in a NTP reactor and to provide thermal protection for the CMC material, in particular the SiC—SiC composite, forming the fuel assembly outer structure 110. The material of the insulation layer 160 should also be chemically compatible with the CMC material. For example, the insulation layer 160 can be formed of a refractory ceramic material. An example refractory ceramic material is zirconium carbide, particularly porous zirconium carbide. In exemplary embodiments, the refractory ceramic material is porous with 60 to 85%, alternatively 70-85% or 72-76% or 78-82%, of the volume consisting of void spaces, and the porosity is selected in order to provide a balance between insulation value and mechanical properties.

In exemplary embodiments, the refractory ceramic material for the insulation layer 160 is zirconium carbide. For example, in one embodiment the zirconium carbide is non-stoichiometric and is deficient in carbon with a maximum carbon content for single phase ZrC_(x) of 0.98. An optimum carbon to zirconium ratio is in the range of 0.85 to 0.96, alternatively in a range of 0.90 to 0.95.

In one example, the refractory ceramic material for the insulation layer 160 is 90% to 99.999% zirconium carbide foam, alternatively 95% to 99.999% zirconium carbide foam. Suitable zirconium carbide foam for the insulation layer 160 is available from Ultramet, Inc. of Pacoima, CA. In another example, the refractory ceramic insulation is in the form of 95% to 99.999% fibrous zirconium carbide. Porous zirconium carbide insulation maintains its functionality to temperatures on the order of 3000K. Thus, the use of porous zirconium carbide insulation allows the use of the CMC structural material over the full length of the fuel assembly outer structure 110.

In some embodiments, the insulation layer 160, which is otherwise porous as disclosed herein, optionally includes a thin, dense layer 165 on its inner surface. In some embodiments, the layer 165 is a zirconium carbide layer that is more dense than the insulation layer 160. The inclusion of such a layer 165 on the inner surface of the insulation layer 160 will increase the overall strength of the insulation layer 160 and protect the insulation layer 160 from contact with the material adjacent to the insulation layer inner surface, i.e., either the fuel assembly intermediate structure (if included) or the elongated fuel elements or the side surface of a unitary, solid fuel element.

Other structures of the carbide-based fuel assembly schematically illustrated in FIGS. 4A and 4B include the fuel assembly outer structure 110. There is a separation distance between the inner surface of the fuel assembly outer structure 110 and the outer surface of the insulation layer 160. The separation distance forms a void space 265 between the adjacent components that contributes to improved heat transfer performance of the carbide-based fuel assembly 100. For example, void space 265 between the inner surface of the fuel assembly outer structure 110 and the outer surface of the insulation layer 160 may contain (non-flowing) hydrogen gas and can provide additional thermal insulation properties. FIGS. 4A and 4B illustrate an embodiment of these separation distances and spaced-apart arrangements, including of void space 265.

In some embodiments, the outer surface of the fuel assembly outer structure 110 optionally includes a barrier coating 175 having a composition including a refractory ceramic material. This barrier coating 175 of refractory ceramic material protects the underlying CMC material from degradation. For example, the outer surface of the fuel assembly outer structure 110 is expected to be exposed to hydrogen at a pressure in excess of 2000 psia (approx. 13.79 MPa). While this hydrogen will be flowing through the coolant channels 220 in the moderator block 210 (see FIG. 5 ), hydrogen may also be present in the void space 270 between the moderator block 210 and the fuel assembly outer structure 110 (as shown in FIG. 4B), but the hydrogen in void space 270 is not expected to be flowing. The barrier coating 175 protects the underlying material of the fuel assembly outer structure 110, e.g., the SiC—SiC composite material, from degradation by minimizing exposure to the high-pressure hydrogen, and to prevent, or at least reduce, flow of relatively cold hydrogen supplied to the moderator block 210 through the structures of the fuel assembly and into the propellant flow stream within the fuel assembly, as such leakage would reduce the temperature of the propellant, and hence reduce the Isp. In particular embodiments, the fuel assembly outer structure 110 is a SiC—SiC composite and a dense SiC barrier coating 175 is added to the outer surface of the SiC—SiC composite material by a suitable method, such as by a chemical vapor deposition technique.

In other embodiments, the outer surface of the fuel assembly outer structure 110 includes a spacer structure 185 projecting from the outer surface. When the carbide-based fuel assembly 100 is assembled in a nuclear fission reactor structure, such as in a fuel assembly opening 205 of a moderator block 210 as shown in FIG. 5 , the spacer structure 185 creates a known, controlled distance between the outer surface of the fuel assembly outer structure 110 and surfaces of the fuel assembly opening 205 in the moderator block 210, forming a gap 270 therebetween.

In still further embodiments, the outer surface of the fuel assembly outer structure 110 includes both a barrier coating 175 having a composition including a refractory ceramic material and a spacer structure 185 projecting from the outer surface. In some embodiments, the functions and the effects of the two features can both be present.

FIGS. 3A and 3B illustrate cylindrical fuel elements 105, but the fuel elements 105 can be made in other geometries, as noted herein. In addition, shapes of the fuel elements 105 can be used that (a) increase surface area to volume ratio, (b) interlock with each other, and (c) enhance propellant/cooling mixing (such as with a twisted shape). For example, a twisted ribbon design for the fuel element 105 can create sufficient openings between the fuel elements 105 for coolant flow, in which case, there may be no need to include wire wraps or other means to create a flow passages between the individual fuel elements 105. Also, the composition and/or length of the fuel elements 105 can be selected to facilitate axially zoning of the fuel enrichment to provide a desired axial power profile.

The fuel element bundles (190 a, 190 b, 190 c) illustrated in the embodiment in FIG. 4A are arranged in that order along the longitudinal axis 140, with fuel element bundle 190 a being (relative to fuel element bundles 190 b, 190 c) an upper fuel element bundle in a section closer to the inlet or first end of the of the carbide-based fuel assembly 100 and fuel element bundle 190 c being (relative to fuel element bundles 190 a, 190 b) a lower fuel element bundle in a section closer to the outlet or second end of the of the carbide-based fuel assembly 100. Also illustrated in FIG. 4A is the stacked nature of the fuel element bundles 190 a, 190 b, 190 c, fuel assembly intermediate structures 250 a, 250 b, 250 c, and support meshes 150 b, 150 c. Additional fuel element bundles can be longitudinally added, e.g., fuel element bundles 190 d, 190 e, . . . , 190 n, each fuel element bundle separated from an adjacent fuel element bundle by a support mesh.

Considering the increasing temperature in each subsequent section as one progresses from the inlet to the outlet of the carbide-based fuel assembly 100, the various materials and structures of the components of the carbide-based fuel assembly 100 can correspondingly change to accommodate the expected increase in temperature in each subsequent section during operation in order to maintain overall operational performance of the carbide-based fuel assembly 100. In some instances, these corresponding changes are implemented based on fuel zoning in the carbide-based fuel assembly 100.

In addition, it is optional whether the first section located at the uppermost section or inlet of the carbide-based fuel assembly 100 has a layer of insulation or not. The CMC material of the fuel assembly outer structure 110 may be capable of providing suitable thermal performance under the temperatures anticipated during initial heating of the coolant.

FIGS. 2A and 4A also illustrate the use of more than one support mesh 150. One advantage of using multiple support meshes 150 is that the individual fuel elements 105 can be substantially shorter than the length of the entire carbide-based fuel assembly 100. In general, the use of (relatively) shorter fuel elements 105 (whether in the form of elongated bodies or monolith bodies), for example, less than a full length of the entire carbide-based fuel assembly 100, less than half the length of the entire carbide-based fuel assembly 100, or less than a quarter of the length of the entire carbide-based fuel assembly 100, facilitates axially zoning of fuel enrichment to provide a desired axial power profile. Additionally, using multiple support mesh 150 obviates the need for complex cross-sectional shapes that would otherwise be needed to support one set of fuel elements atop the below sets of fuel elements (or, stated otherwise, without the need for complex cross-sectional shapes for the fuel elements that would be needed to support a first fuel element bundle atop a second fuel element bundle). The use of multiple support meshes 150 also eliminates the need for precise alignment of the flow volume from one section of fuel elements to the adjacent section, particularly when the fuel elements are in the form of monolithic bodies containing flow channels. Further, the presence of a support mesh 150 between sections within the carbide-based fuel assembly 100 enhances the probability of continued operation with damaged fuel elements, because the sections would be independently supported by the associated support mesh(es). For example, the support meshes between sections would limit any debris from damaged fuel elements to the one affected section, rather than allowing the debris to move throughout successive sections of the fuel assembly.

As an alternate for forming a controlled void space and/or controlled gap between layers of the carbide-based fuel assembly 100, one can insert a space-forming structure, such as a thin-wall, wavy tube, between any two structures, i.e., a) between the fuel element bundles 190 and fuel element intermediate structure 250, b) between the fuel element intermediate structure 250 and the insulation layer 160, and c) between the insulation layer 160 and the fuel assembly outer structure 110. A space-forming structure can also be positioned between the outer surface of the fuel element outer structure and the inner surface of the fuel element openings to form a controlled void space and/or controlled gap between those structures.

In embodiments in the form of a thin-wall, wavy tube, fabrication may be accomplished by drawing a thin-wall tube of an appropriate metal alloy, such as Zircaloy or a 300 series stainless steel with the required formability, though a rotating die with a synchronously rotating mandrel supporting the tube inner diameter to produce undulations longitudinally along the tube wall. Rotation will create a spiral of the raised ridges. The diameter of the wavy tube is suitable for placing the tube between the noted layers/noted structures and the height of the undulation (ridges) will be such that it fits within the void space/gap. It is also noted that the wavy geometry of such a tube provides compliance for differential thermal expansion between the adjacent components during heat-up and cool-down and also provides additional mechanical support to adjacent components. Also, any modulated surface can be used for the wavy surface of the tube. Depending on the material of the thin-wall, wavy tube, use of the thin-wall, wavy tube as a space-forming structure may be limited to locations within the fuel assembly 100 that are at suitable temperatures to prevent loss of structural integrity and/or loss of function, such as by melting and/or softening.

In operation, the propellant, such as hydrogen, enters the carbide-based fuel assembly 100 at an upper end, for example via inlet flow adapter 120, and is heated by flowing past the fuel elements 105 and exits the carbide-based fuel assembly 100 at the lower end, for example via outlet flow adapter 125. The various structures and spacing illustrated in example embodiments in FIGS. 4A and 4B, particularly if made of the noted materials, serves to separate the fuel and the hot propellant from the moderator material. Consequently, while the propellant temperature toward the lower end of the carbide-based fuel assembly 100 may exceed 2900K, the temperature at the outer surface of the carbide-based fuel assembly 100 adjacent to the moderator block 210 will be less than about 800K.

FIG. 5 schematically illustrates, in a radial cross-sectional view, an embodiment of a carbide-based fuel assembly 100 in a nuclear fission reactor structure. In the FIG. 5 embodiment, the fuel element is in the form of a solid monolithic fuel body 200 containing flow channels 201, but other embodiments could use fuel elements in the form of elongated bodies (for example, as shown and described with regard to FIGS. 2A-B). The illustrated radial cross-sectional view shows a portion of a plane perpendicular to a longitudinal axis of the nuclear fission reactor structure. Centrally located within the FIG. 5 view is one carbide-based fuel assembly 100. Portions of additional fuel assemblies 100 a-f are also shown in FIG. 5 and are distributively arranged in the moderator block 210. In particular, the moderator block 210 includes a plurality of fuel assembly openings 205 and each one of the plurality of fuel element assemblies 100 is located in a different one of the plurality of fuel assembly openings 205.

As seen in FIG. 5 and as previously noted, exemplary embodiments of the carbide-based fuel assembly 100 include a fuel assembly intermediate structure 250 about an envelope surface of the fuel element(s) in that section of the carbide-based fuel assembly 100. Depending on the fuel form, the inner surface of the fuel assembly intermediate structure 250 can be spaced apart from the outer surface of the envelope to form a gap. The fuel assembly intermediate structure 250 is outward of the outer surface of the fuel element envelope. Where the fuel form is a plurality of elongated fuel bodies, the gap is in fluid communication with the coolant flow volume 115 and coolant, such that propulsion gas traveling through the carbide-based fuel assembly 100 also flows in the gap. Where the fuel form is a solid monolithic body, the gap is minimized. If present, however, the gap can contain non-flowing gas, such as hydrogen, and can serve as thermal insulation to the carbide-based fuel assembly 100.

Exemplary embodiments of the carbide-based fuel assembly 100 also include an insulation layer 160, which is interposed between the outer surface of the fuel assembly intermediate structure 250 and an inner surface of the fuel assembly outer structure 110, a void space 255 between the inner surface of the insulation layer 160 and the outer surface of the fuel assembly intermediate structure 250 and which is shown with ribs 260, a void space 265 between the outer surface of the insulation layer 160 and the inner surface of the fuel assembly outer structure 110, and gap 270 between the outer surface of the fuel assembly outer structure 110 and the inner surface of the fuel assembly opening 205 within the moderator block 210. As seen in FIG. 5 , each of the void space 255, void space 265, and gap 270 have the form of an annulus in the depicted embodiment.

FIG. 5 also illustrates the spatial relationship of the carbide-based fuel assembly 100 and the fuel assembly openings 205 (defined by periphery 225) in the moderator block 210. In particular, in the illustrated embodiment, the outer surface of the fuel assembly outer structure 110 is spaced apart from the inner surface of the fuel assembly openings 205 in the moderator block 210. This spaced-apart relationship forms gap 270. This gap 270 is outside of the carbide-based fuel assembly 100 and may optionally contain (non-flowing) hydrogen gas and can provide additional thermal insulation properties.

The moderator block 210 occupies the space between the fuel assemblies 100. The moderator block 210 is typically a monolithic body having a composition capable of thermalization (or moderation) of neutrons formed in the fuel assembly 100. Thermalization reduces the energy of the neutrons to values in the range of 1 eV. In exemplary embodiments, the moderator block 210 has a composition including zirconium hydride, beryllium, beryllium oxide, yttrium hydride, graphite or combinations thereof. In a specific embodiment, the moderator block 210 has a composition including zirconium hydride, in particular zirconium hydride in which the H to Zr ratio ranges from 1.85 to 1.95, e.g., ZrH_(1.85) to ZrH_(1.95), such as ZrH_(1.9).

The moderator block 210 includes a plurality of moderator block coolant channels 220. The moderator block coolant channels 220 extend longitudinally parallel to the longitudinal axis of the nuclear fission reactor structure (which is typically parallel to the longitudinal axis 140 of the carbide-based fuel assembly 100) from a first end surface of the moderator block 210 to a second end surface of the moderator block 210. The longitudinal axis of the nuclear fission reactor structure is typically parallel to the longitudinal axis 140 of the carbide-based fuel assembly 100. Depending on the distribution of carbide-based fuel assemblies 100 at or about the longitudinal axis of the nuclear fission reactor structure, the longitudinal axes of the carbide-based fuel assemblies 100 and the reactor may or may not be colinear to achieve a symmetric distribution of fuel assemblies 100 about the reactor axis. The embodiment in FIG. 5 , however, does show longitudinal axis 140 of the carbide-based fuel assembly 100 coincident with the longitudinal axis of the nuclear fission reactor structure.

The plurality of moderator block coolant channels 220 are in spaced-apart relation to, and distributed about, the periphery 225 of each of the plurality of fuel assembly openings 205 in the moderator block 210. The spacing and distribution of the moderator block coolant channels 220 are generally governed by thermal management and neutronics of the carbide-based fuel assembly 100 and of the nuclear fission reactor structure. In the example embodiment shown in FIG. 5 , the moderator block coolant channels 220 are approximately 2 to 6 millimeters (mm) in diameter, alternatively 4 to 6 mm in diameter, and are distributed circumferentially about the periphery 225 of the fuel assembly openings 205 and are spaced within 2 to 12 mm, such as within 2 to 6 mm or within 6 to 12 mm, of the periphery 225.

In some embodiments, the moderator block is a single, solid unitary structure. In other embodiments, the moderator block consists of a plurality of moderator block sections that are arranged next to and/or on top of each other to form the overall structure of the moderator block. In which case, the moderator block can be built up from a plurality of moderator block sections. For example, it is also contemplated that there are multiple horizontally arranged layers of moderator block and that each horizontal layer of moderator block will be further subdivided into sections that are arranged next to each other. FIG. 4A illustrates two moderator block sections 210 a and 210 b as horizontal slabs that are stacked on top of each other in a longitudinal arrangement.

When describing both the arrangement of the plurality of fuel elements 105 in the carbide-based fuel assembly 100 and the arrangement of the carbide-based fuel assemblies 100 in the moderator block 210, distributively arranged means in substantially uniformly spaced relationship and with a repetitive or symmetry pattern consistent with the neutronics and thermal management requirements of the fuel assembly and/or the nuclear fission reactor structure. As an example, fuel assemblies 100 a-f in FIG. 5 are arranged in a hexagonal pattern around central fuel assembly 100. As another example and as shown in FIG. 3B in which there are a plurality of fuel elements each in the form of an elongated fuel body, i.e., carbide-based fuel rods, the innermost ring of fuel elements is arranged in a hexagonal pattern around a central fuel element 105 a, with fuel elements outward thereof in circular rings. Other distributive arrangements for the fuel elements can be utilized, including other axisymmetric arrangements, such as based on a triangle, a square, a circle, an octagon or a decagon. It is also noted that in FIG. 3B, the central fuel element 105 a is coincident with the longitudinal axis 140 of the carbide-based fuel assembly 100. This distributive arrangement also extends to the flow channels 201 in fuel elements having the form of a solid monolithic fuel body 200 and, in the example illustrated in FIG. 5 , a central flow channel 201 a in the solid monolithic fuel body 200 is coincident with the longitudinal axis 140 of the carbide-based fuel assembly 100 and additional flow channels 201 are arranged in a hexagonal pattern around the central flow channel 201 a, with flow channels outward thereof in circular rings. Other distributive arrangements for the flow channels can be utilized, including other axisymmetric arrangements, such as based on a triangle, a square, a circle, an octagon or a decagon. The distributive arrangement of the fuel elements 105 in the carbide-based fuel assembly 100, the distributive arrangement of the flow channels 201 in the solid monolithic fuel body 200 in the carbide-based fuel assembly 100, and the distributive arrangement of the carbide-based fuel assemblies 100 in the moderator block 210 may or may not be identical.

Also, in alternative embodiments and depending on Isp, the fuel elements 105 can be cylindrical in shape and can be arranged in the carbide-based fuel assembly 100 in a closed-packed arrangement.

In one particular embodiment, the fuel elements 105 (e.g., in the form elongated fuel bodies) have a diameter of 2 to 3 millimeters (mm) and are circumferentially spaced (from nearest fuel elements at the same radial distance from the longitudinal axis 140) at a distance of 1 to 5 mm and are radially spaced (from nearest fuel elements at the next radially inward and next radially outward position) at a distance of 1 to 10 mm. In one particular embodiment, the envelope of the fuel element bundle, e.g., rods making up a bundle, has a diameter of 45 to 60 mm, alternatively 50 to 56 mm, the fuel assembly intermediate structure 250 (if present) has a thickness in the radial direction of 1 to 4 mm, alternatively 1 to 3 mm, the insulation layer 160 has a thickness in the radial direction of 2 to 6 mm, alternatively 2 to 4 mm, the layer 165 (if present) has a thickness in the radial direction of less than 1 mm, the fuel assembly outer structure 110 has a thickness in the radial direction of 2 to 6 mm, alternatively 2 to 4 mm. When present, the barrier coating 175 has a thickness in the radial direction of less than 1 mm. The void space 255 and gaps 265 and 270 are each 0.3 to 0.6 mm.

In one particular embodiment, the envelope of the fuel element (e.g., in the form of a monolith with coolant channels) has a diameter of 45 to 60 mm, alternatively 50 to 56 mm, the fuel assembly intermediate structure 250 (if present) has a thickness in the radial direction of 1 to 4 mm, alternatively 1 to 3 mm, the insulation layer 160 has a thickness in the radial direction of 2 to 6 mm, alternatively 2 to 4 mm, the layer 165 (if present) has a thickness in the radial direction of less than 1 mm, the fuel assembly outer structure 110 has a thickness in the radial direction of 2 to 6 mm, alternatively 2 to 4 mm. When present, the barrier coating 175 has a thickness in the radial direction of less than 1 mm. The void space 255 and gaps 265 and 270 are each 0.3 to 0.6 mm.

However, the dimensions for the various features, structures, and components can vary according to design aspects, such as neutronics, thermohydraulics, weight and space requirements.

Also, the additional carbide-based fuel assemblies 100 a-f have similar features and arrangement of features as described with respect to carbide-based fuel assembly 100.

The fuel elements can be manufactured by suitable means. In the following example, a fabrication process to produce an example ternary carbide fuel element with the chemical composition (U,Zr,Nb)C is described. Although the carbide is implied to be a solid solution monocarbide, a substoichiometric composition somewhat deficient in carbon may also be used. Additionally, process variations may be included that still achieve a suitable fuel element 105.

The fabrication process for a fuel element 105 generally consists of several steps. In the first step, constituent material powders are prepared. For the example chemical composition (U,Zr,Nb)C, the constituents would include zirconium carbide, niobium carbide, a uranium containing compound, and an organic binder. Additional constituents may include graphite and/or a liquid phase sintering aid such as nickel.

The refractory metal carbides, zirconium carbide and niobium carbide, can be fabricated as monocarbide powders using conventional processes. The uranium containing compound can be uranium carbide or uranium hydride, depending on the desired carbon content of the fabricated carbide. When uranium hydride is used, graphite is also added. Overall carbon content is controlled by the atomic ratio of uranium to added graphite. The particle sizes of all constituent powders are rendered sufficiently fine by comminution.

After the constituent materials are prepared, they are blended into a uniform mixture for green body formation. One method for green body formation is extrusion. Green bodies of elements with simple geometries, such as circular cylinders or non-helical elements with convex polygon cross sections, may also be formed by rolling, depending on the rheology of the green body mixture.

After green body formation, the bodies are rendered into a dense state using high temperature sintering. Target density for a fuel element is generally at least 95% of its theoretical density (i.e., less than 5% porosity). In sintering, the green parts are heated to a very high temperature for a short period of time to develop a dense microstructure. Densification can be accelerated by the presence of a liquid phase sintering aid. In the case where uranium is added to the element material in the form of uranium hydride, the uranium hydride dissociates into uranium and hydrogen, the latter of which is outgassed from the part. The uranium and added graphite react to form uranium carbide, which is molten above about 2800K and is an effective liquid phase sintering aid. In the case where uranium is added in the form of uranium carbide, nickel can also be added. Nickel is an effective liquid phase sintering aid at temperatures above its melting temperature of about 1730K.

Although a small to moderate degree of homogenization in chemical composition does occur during liquid phase sintering, the element material in the densified body after sintering is still typically compositionally non-uniform. Therefore, following densification, the sintered densified body is held at temperatures in the range of 2400K to 2600K for an extended period (on the order of hours, e.g., 2 to 5 hours) to homogenize the chemical composition. If nickel is used as a liquid sintering aid, this heated homogenization step removes the nickel from the element material by evaporation at temperatures greater than about 2300K.

Once cooled, the fuel element 105 can optionally be refractory carbide coated by, for example, a vapor deposition technique.

The fuel assemblies 100 can be manufactured by suitable means. General steps in an example method S280 of manufacturing a carbide-based fuel assembly are shown in the flow chart in FIG. 6 . In step S282, a fuel assembly outer structure 110, such as a SiC—SiC composite structure, is fabricated by a suitable means. To facilitate later attachment of the inlet flow adapter 120 to the inlet end of the fuel assembly outer structure 110, an attachment component (such as a flange or short pipe section or a sleeve), typically formed of a metal alloy, is S284 attached to the inlet end by, for example, vacuum brazing or other process that can produce an essentially leak-tight joint. The components internal to the fuel assembly outer structure 110 are then inserted in a suitable order to achieve the desired location of each component within the fuel assembly outer structure 110 as well as positioning relative to each other, i.e., radially inward or outward, longitudinally stacked or not.

Thus, in one aspect, a support mesh 150, such as a disc-shaped zirconium carbide and/or niobium carbide porous body which has been previously manufactured, is S286 inserted into the fuel assembly outer structure 110 and seated on an associated support feature toward the outlet end of the fuel assembly outer structure 110 such that the first inserted support mesh 150 is a lower support mesh (relative to others in the fuel assembly 100). An insulation body, such as a tubular zirconium carbide insulation body which has been previously manufactured, is S288 inserted into the fuel assembly outer structure 110 and seated on an upper surface, preferably the outer region 158, of the support mesh 150 to form the insulation layer 160. A fuel assembly intermediate body, such as a tubular zirconium carbide-graphite or niobium carbide-graphite body which has been previously manufactured by a suitable means, is S290 inserted into the fuel assembly outer structure 110 inward of the insulation layer 160 and seated on an upper surface, preferably the outer region 158, of the support mesh 150 to form the fuel assembly intermediate structure 250.

Fuel, either (i) elongated fuel bodies individually or pre-assembled into a fuel element bundle or (ii) one or more fuel monolith bodies, such as a cermet fuel body or a carbide-based fuel body, are S292 inserted into the fuel assembly outer structure 110 in the space defined by the inner surface of the fuel assembly intermediate structure 250 and seated on an upper surface of the support mesh 150. After the fuel for a particular section has been positioned, a support mesh 150 is S294 inserted as an upper support mesh for that section. Additional insulation bodies forming the insulation layer 160, fuel assembly intermediate structures 250, fuel, and support mesh 150 can be added for subsequent sections in a cyclic process S296. After inserting the final fuel and the final support mesh 150 into the fuel assembly outer structure 110, the inlet flow adapter 120 is S298 attached to the inlet end of the fuel assembly outer structure 110 via the previously attached attachment component.

Alternative embodiments can replace separate insulation layers 160 for each section with a single continuous insulation component that forms an insulation layer 160 for the entire fuel assembly 100. An example of an outer single continuous insulation layer 160 spanning multiple sections is depicted in FIG. 4A.

In additional aspects, the spacing of the fuel elements 105 so as to form the desired flow volume 115 is by suitable means. In one example applicable to fuel elements 105 in the form of an elongated fuel body to be arranged in a fuel element bundle, each fuel element 105 is wrapped with a refractory metal “wire” that is compatible with the material of the fuel element 105 and stable at the reactor operating conditions. The wire can be wrapped around each fuel element 105 using a helical pattern, preferably having a wide pitch. When the fuel elements are assembled into a fuel element bundle, the wire wrap around each fuel element 105 will make limited contact with the wire wrap around adjacent fuel elements 105, creating a space around each fuel element 105 that is part of the flow volume 115 that permits flow of coolant during reactor operation. The wire wrap around the fuel elements 105 located at the perimeter of the fuel element bundle also contributes to space those fuel elements 105 from the insulation layer 160, or the intermediate structure (if present), and thereby also contributes to creating a space to permit coolant flow.

In another example, fuel elements 105 having regular (or irregular) polygonal cross-sectional shapes and with a helical protrusion, such as a “twisted-ribbon” rod design, can be used to create the flow volume 115. This method may optionally be combined with wire wrap to hold the fuel elements 105 together in the fuel bundle and to also create the flow volume 115.

In a further example, appropriately-sized blind holes on the surface(es) of the support mesh(es) 150 can be made. Inserting ends of the fuel elements 105 into the blind holes can restrain the fuel elements 105 in position. The blind holes can be created by suitable machining methods and the thickness of the support mesh may be increased to accommodate the blind holes. To ensure proper positioning of the fuel elements 105 during assembly, an assembly fixture can be optionally used to assist in fuel element 105 positioning and for ease in mating to the blind holes. The material of the assembly fixture can be removed by heating to relatively low temperatures.

All components discussed above are fabricated to required specifications, including meeting dimension tolerances. It is also noted that the above method S280 for manufacturing a carbide based fuel assembly is applicable to, and can be extend to, other fuel forms, including solid carbide or cermet fuel bodies containing flow channels or cercer fuel bodies containing flow channels.

The carbide-based fuel assemblies disclosed herein can be incorporated into a nuclear fission reactor structure. In general, the carbide-based fuel assemblies are positioned within a block of moderator material used to thermalize fast neutrons. Nuclear control means such as rotating peripheral control drums can be used to control the reactivity of the core. The entire core is located within a pressure boundary connected to a converging-diverging nozzle.

FIG. 7 schematically illustrates, in a cross-section parallel to the reactor axis, an embodiment of a nuclear fission reactor structure within a NTP reactor. Embodiments of the nuclear fission reactor structure 300 includes a plurality of carbide-based fuel assemblies 100 (for example, any one of the carbide-based fuel assembly embodiments disclosed herein) located within an active core region 305 of the nuclear fission reactor structure 300 (the active core region 305 being the internal region where the moderator block is located and the fuel assembly portions within the moderator block). At the inlet and the outlet of the fuel assemblies 100, connection assemblies (such as inlet connection assembly 310 and outlet connection assembly 315) provide fluid communication for propellant supplied to and exhausted from each of the carbide-based fuel assemblies 100. Thus, the inlet connection assemblies 310 connect to or interface with entrance openings 130 of the plurality of fuel assemblies 100 and the outlet connection assemblies 315 connect to or interface with exit openings 135 of the plurality of carbide-based fuel assemblies 100.

An interface structure 340, which may or may not include supplemental radial restraint, is radially outward of the active core region 305 and a reflector 320 is radially outward of the interface structure 340. A first surface of the interface structure 340 is conformal to the outer surface of the active core region 305 and a second surface of the interface structure 340 is conformal to an inner surface of the reflector 320. The inner surface of the reflector 320 is oriented toward the active core region 305, and the interface structure 340 functions to mate the geometry of the outer surface of the active core region 305 to the geometry of the inner surface of the reflector 320, thus allowing various arrangements for the carbide-based fuel assemblies 100 in the moderator block 210, such as a hexagonal pattern leading to a hexagonal interface with the interface structure 340 or a concentric ring pattern leading to a circular interface with the interface structure 340.

FIG. 8 is a schematic, cross-sectional, top view of an embodiment of an embodiment of a nuclear propulsion fission reactor structure 300 within a vessel 325. A plurality of control drums 330, each including a neutron absorber body 335, is located within a volume of the reflector 320, such as in an annular section on the outer portion of the cylindrically shaped control drum. The control drum 335 itself is made of a neutron reflecting material, similar to the reflector 320. The neutron absorber body 335 is made of a neutron absorbing material and is movable, such as by rotation, between a first position and a second position, the first position being radially closer to the active core region than the second position. In exemplary embodiments, the first position is radially closest to the active core region and the second position is radially farthest from the active core region. The neutron absorber body 335 is movable between the first position and the second position to control the reactivity of the active core region 305. In the illustrated example, the neutron absorber body 335 is rotatable from the first, radially closer position, to the second position by rotation (R) around an axis of the control drums 330. However, other radial positions and/or movement directions can be implemented as long as the various positions to which the neutron absorber body 335 can be moved provides control of the reactivity of the active core region 305. In some embodiments, when the plurality of neutron absorber bodies 335 are each at the first, radially closer position, each of the plurality of neutron absorber bodies 335 are radially equidistant from the axial centerline of the active core region 305. Other control concepts can also be implemented, such as regulating neutron leakage by opening and closing portions of the reflector 320.

The reflector 320 primarily functions to “reflect” neutrons back into the active core region to maintain criticality and reduces “leakage” of neutrons. Neutrons escaping from the reactor have no chance to generate fission reactions, lowering the criticality potential of the nuclear fission reactor structure. Secondarily, the reflector 320 houses the control drums 330 with the neutron absorber bodies 335, which are the primary system for reactivity control. In FIGS. 7 and 8 , the embodiment of a reflector 320 is in the form of an annulus with rotatable control drums 330 including a section with a neutron absorber body 335. In order to house sufficiently sized rotatable control drums 330 with sufficiently sized neutron absorber bodies 335 to control reactivity, the annulus of the reflector 320 cannot be overly thin (in width (W) between an inner surface and an outer surface). In exemplary embodiments, the width (W) is 10 cm to 30 cm for a beryllium-based reflector. The width may vary based on the materials of the reflector 320 and, if applicable, the weight requirements for non-terrestrial applications of the nuclear fission reactor structure. Materials with lower neutron reflecting properties require a thicker reflector, i.e., a larger width (W).

The nuclear fission reactor structure can further comprise a vessel 325. FIGS. 7 and 8 schematically illustrate an embodiment of a nuclear fission reactor structure 300 with a vessel 325. The nuclear fission reactor structure 300, which includes the active core region 305, the interface structure 340, the inlet connection assembly 310 and outlet connection assembly 315, the reflector 320, and the plurality of control drums 330 with neutron absorber bodies 335, is housed within an interior volume of the vessel 325.

As shown in FIG. 7 , motors 350 are operatively attached for rotation to the control drums 330 by a drum shaft 355. Motors 350 may be housed in pressure boundary extensions of the vessel 325 or alternatively may not be, in which case seals are required around the drum shafts 355. Motors internal to the vessel 325 can also be implemented.

Embodiments of the vessel 325 are formed from machined forgings and generally use high strength aluminum or titanium alloys due to weight considerations. The vessel 325 can be multiple components that are then assembled together, for example, with fasteners. However, in other embodiments, the vessel 325 can be one contiguous component or a welded together assemblage.

Additional disclosure related to the nuclear fission reactor structure and its components can be found in U.S. patent application Ser. No. 16/999,244, the entire contents of which are incorporated by reference.

The disclosure is also directed to a nuclear thermal propulsion engine that includes the nuclear fission reactor structure 300 within a vessel 325. The nuclear thermal propulsion engine further includes shielding, turbo machinery, and a nozzle section attached to or supported by the vessel 325, for example, as consistent with that shown and described in connection with FIG. 1 .

It is contemplated that various supporting and ancillary equipment can be incorporated into the disclosed nuclear fission reactor structure and nuclear thermal propulsion engine. For example, at least one of a moderator (such as a zirconium hydride, beryllium, beryllium oxide, and graphite), a control rod for launch safety, a neutron source to assist with start-up, and a scientific instrument (such as a temperature sensor or radiation detector) can be incorporated into the nuclear propulsion fission reactor structure.

The disclosed arrangements pertain to any configuration in which a heat generating source including a fissionable nuclear fuel composition, whether a fuel element or a plurality of fuel elements, is incorporated into a fuel assembly. Although generally described herein in connection with a gas-cooled nuclear thermal propulsion reactors (NTP reactors), the structures and methods disclosed herein can also be applicable to other fission reactor systems.

Nuclear propulsion fission reactor structure disclosed herein can be used in suitable applications including, but not limited to, non-terrestrial power applications, space power, space propulsion, and naval applications, including submersibles.

While reference has been made to specific embodiments, it is apparent that other embodiments and variations can be devised by others skilled in the art without departing from their spirit and scope. The appended claims are intended to be construed to include all such embodiments and equivalent variations. 

What is claimed is:
 1. A fuel assembly, comprising: a fuel assembly outer structure; a fuel assembly intermediate structure; a fuel element contained within the fuel assembly intermediate structure, wherein the fuel element includes one or more fuel bodies containing a uranium-based fuel composition, wherein the fuel assembly intermediate structure is spaced apart from an outer envelope surface of the fuel element and extends parallel to the fuel element from a first end surface of the fuel element to a second end surface of the fuel element, an inner surface of the fuel assembly intermediate structure is oriented toward the fuel element, and an outer surface of the fuel assembly intermediate structure is oriented away from the fuel element; an insulation layer interposed between an inner surface of the fuel assembly outer structure and the outer surface of the fuel assembly intermediate structure; a first void space between an outer surface of the insulation layer and the inner surface of the fuel assembly outer structure; and a second void space between an inner surface of the insulation layer and the outer surface of the fuel assembly intermediate structure, wherein the fuel assembly intermediate structure is formed of a refractory ceramic-graphite composite material.
 2. The fuel assembly according to claim 1, wherein the one or more fuel bodies are in the form of a plurality of elongated fuel bodies, wherein each of the elongated fuel bodies contains the uranium-based fuel composition, and wherein the plurality of elongated fuel bodies are arranged in a fuel bundle, wherein each elongated fuel body longitudinally extends from a first end to a second end along a longitudinal axis of the respective elongated fuel body, wherein the plurality of elongated fuel bodies are arranged in spaced-apart relationship relative to each other, and wherein an empty space between the spaced-apart plurality of elongated fuel bodies in the fuel bundle forms at least part of a coolant flow volume through which a coolant in a form of a propellant gas is able to flow during operation of a reactor containing the fuel assembly.
 3. The fuel assembly according to claim 2, wherein the fuel assembly is elongated and is tubular-shaped and has an axial centerline defining a longitudinal axis of the fuel assembly, wherein the plurality of elongated fuel bodies of the fuel element are located at positions that are axisymmetric about the longitudinal axis of the fuel assembly, as seen in cross-section in a plane perpendicular to the longitudinal axis of the fuel assembly.
 4. The fuel assembly according to claim 3, wherein, in a plane perpendicular to the longitudinal axis of the elongated fuel body, a cross-sectional shape of the elongated fuel body is a polygon, a circle, or an oval.
 5. The fuel assembly according to claim 2, wherein the uranium-based fuel composition includes a binary carbide containing uranium or a ternary carbide containing uranium.
 6. The fuel assembly according to claim 5, wherein the fuel element is refractory carbide coated.
 7. The fuel assembly according to claim 2, wherein the uranium-based fuel composition includes UC—ZrC.
 8. The fuel assembly according to claim 2, wherein the uranium-based fuel composition includes UC—ZrC—NbC.
 9. The fuel assembly according to claim 2, wherein the uranium-based fuel composition is carbide-based and wherein the fuel element is refractory carbide coated.
 10. The fuel assembly according to claim 2, wherein the insulation layer extends between a first end surface of a first fuel element bundle and a second end surface of the first fuel element bundle.
 11. The fuel assembly according to claim 10, further comprising a first support mesh located at the first end surface of the first fuel element bundle and a second support mesh located at the second end surface of the first fuel element bundle.
 12. The fuel assembly according to claim 11, wherein each support mesh includes a first region having a plurality of openings, and wherein the plurality of openings are interconnected internally within the first region and form a flow path from a first side to a second side of the support mesh.
 13. The fuel assembly according to claim 12, wherein each support mesh is formed of a third refractory ceramic material, and wherein the third refractory ceramic material is a zirconium-carbide refractory ceramic material or a niobium-carbide refractory ceramic material.
 14. The fuel assembly according to claim 11, wherein a first end surface of the fuel assembly intermediate structure abuts an outer region of the first support mesh and a second end surface of the fuel assembly intermediate structure abuts an outer region of the second support mesh.
 15. The fuel assembly according to claim 11, further comprising a second fuel element bundle, wherein, in a direction of the longitudinal axis of the fuel assembly, the second fuel element bundle is separated from the first fuel element bundle by one of the first support mesh and the second support mesh.
 16. The fuel assembly according to claim 15, further comprising a third support mesh, wherein the third support mesh is located at an opposite end of the second fuel element bundle from the one first or second support mesh separating the second fuel element bundle from the first fuel element bundle.
 17. The fuel assembly according to claim 15, wherein the fuel assembly intermediate structure spaced apart from the envelope surface of the first fuel element bundle is a first fuel assembly intermediate structure, and the fuel assembly further comprises a second fuel assembly intermediate structure, wherein the second fuel assembly intermediate structure is spaced apart from an envelope surface of the second fuel element bundle.
 18. The fuel assembly according to claim 17, wherein a first end surface of the second fuel assembly intermediate structure abuts an outer region of the second support mesh and a second end surface of the second fuel assembly intermediate structure abuts an outer region of the third support mesh.
 19. The fuel assembly according to claim 1, wherein the one or more fuel bodies are in the form of one or more fuel monolith bodies, wherein each fuel monolith body contains the uranium-based fuel composition, and wherein each fuel monolith body includes one or more coolant flow channels, and wherein the one or more coolant flow channels forms at least part of a coolant flow volume through which a coolant in a form of a propellant gas is able to flow during operation of a reactor containing the fuel assembly.
 20. The fuel assembly according to claim 19, wherein the one or more fuel monolith bodies are in a form of a wafer, a layer, a pie-shaped section, or a cylinder.
 21. The fuel assembly according to claim 19, wherein the fuel monolith body includes a carbide matrix in which the uranium-based fuel composition is distributed.
 22. The fuel assembly according to claim 21, wherein the uranium-based fuel composition includes a binary carbide containing uranium or uranium nitride.
 23. The fuel assembly according to claim 22, wherein the fuel element is refractory carbide coated.
 24. The fuel assembly according to claim 22, wherein the binary carbide containing uranium includes (U,Zr)C.
 25. The fuel assembly according to claim 21, wherein the uranium-based fuel composition includes UC—ZrC or UN.
 26. The fuel assembly according to claim 19, wherein the fuel monolith body includes a refractory metal matrix in which the uranium-based fuel composition is distributed.
 27. The fuel assembly according to claim 26, wherein the uranium-based fuel composition includes uranium nitride.
 28. The fuel assembly according to claim 26, wherein the fuel monolith body is refractory metal coated.
 29. The fuel assembly according to claim 1, wherein the uranium-based fuel composition includes uranium having a U-235 assay above 5 percent and below 20 percent.
 30. The fuel assembly according to claim 1, wherein the refractory ceramic-graphite composite material is a zirconium carbide-graphite composite material or a niobium carbide-graphite composite material.
 31. The fuel assembly according to claim 1, wherein the outer surface of the fuel assembly intermediate structure includes one or more ribs projecting outward from the outer surface of the fuel assembly intermediate structure, and wherein the one or more ribs extend axially along a longitudinal length of the fuel assembly intermediate structure or extend helically along a longitudinal length of the fuel assembly intermediate structure.
 32. The fuel assembly according to claim 1, wherein the inner surface of the insulation layer includes one or more ribs projecting outward from the inner surface of the insulation layer, and wherein the one or more ribs extend axially along a longitudinal length of the insulation layer or extend helically along a longitudinal length of the insulation layer.
 33. The fuel assembly according to claim 1, wherein the insulation layer extends from first end to second end of the fuel assembly.
 34. The fuel assembly according to claim 1, wherein the fuel assembly outer structure is formed of a ceramic matrix composite material, and wherein the insulation layer is formed of a first refractory ceramic material.
 35. The fuel assembly according to claim 34, wherein the ceramic matrix composite material is a SiC—SiC matrix composite.
 36. The fuel assembly according to claim 34, wherein the first refractory ceramic material is porous with 60 to 85% of the volume consisting of void spaces.
 37. The fuel assembly according to claim 34, wherein the first refractory ceramic material is 90% to 99.999% zirconium carbide having an open-cell foam structure or is 95% to 99.999% fibrous zirconium carbide.
 38. The fuel assembly according to claim 34, wherein the inner surface of the insulation layer incudes a layer of zirconium carbide that is more dense than the insulation layer.
 39. The fuel assembly according to claim 34, wherein the outer surface of the fuel assembly outer structure includes (a) a layer having a composition including a second refractory ceramic material, (b) a spacer structure projecting from the outer surface, or a combination of (a) and (b).
 40. The fuel assembly according to claim 39, wherein the outer surface of the fuel assembly outer structure includes (a), and wherein the second refractory ceramic material is a SiC refractory ceramic material.
 41. A nuclear fission reactor structure, comprising: a moderator block including a plurality of fuel assembly openings; and a plurality of fuel assemblies according to claim 1, each of the plurality of fuel assemblies located in a different one of the plurality of fuel assembly openings, wherein, in a cross-section of the moderator block perpendicular to a longitudinal axis of the nuclear fission reactor structure, the plurality of fuel assemblies are distributively arranged in the moderator block.
 42. The nuclear fission reactor structure according to claim 41, further comprising: a plurality of moderator block coolant channels; and a gas gap between an inner surface of the fuel assembly openings and an outer surface of the fuel assembly outer structure, wherein the moderator block coolant channels extend in a longitudinal direction relative to the longitudinal axis of the nuclear fission reactor structure from a first end surface of the moderator block to a second end surface of the moderator block, and wherein the plurality of moderator block coolant channels are in spaced-apart relation to, and distributed about, a periphery of each of the plurality of fuel assembly openings.
 43. A nuclear thermal propulsion engine, comprising: the nuclear fission reactor structure claim 41; shielding; a reservoir for cryogenically storing a propulsion gas; turbomachinery; and a nozzle, wherein, in a flow path of the propulsion gas, the shielding, the turbomachinery, and the reservoir are operatively mounted upstream of an inlet connection assembly, wherein, in the flow path of the propulsion gas, the nozzle is operatively mounted downstream of an outlet connection assembly, and wherein the nozzle provides a flow path for heated propulsion gas exiting the nuclear fission reactor structure. 